05000301/LER-1997-001, Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake

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Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake
Person / Time
ML20134H773
Site:	Point Beach
Issue date:	02/06/1997
From:	Dante Johnson WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134H776	List: 05000301/LER-1997-001, Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake 05000301/LER-1997-001-01, :on 970107,containment Liner Clearance Was Not IAW Plant Design Basis.Caused by Void Between Containment Liner & Concrete Containment Structure.Inspected Containment
References
PBL-97-0042, PBL-97-42, NUDOCS 9702110460
Download: ML20134H773 (1)
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LER-1997-001, Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake

Event date:
Report date:
3011997001R00 - NRC Website
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text

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l Wisconsin Electnc POWER COMPANY F

Point Beoch Nuclear Plant (414) 755-2321 6610 Nuclear Rd., Two Rivers. WI 54241 i

PBL 97-0042 February 6,1997 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington, D. C. 20555 Ladies / Gentlemen:

DOCKET 50-301 LICENSEE EVENT REPORT 97-001-00 CONTAINMENT LINER CLEARANCE NOT IN l

ACCORDANCE WITH PLANT DESIGN BASIS POINT BEACH NUCl. EAR PLANT. UNIT 2 i

Enclosed is Licensee Event Report 97-001-00 for Point Beach Nuclear Plant, Unit 2. This report is provided in accordance with 10 CFR 50.73(aX2XiiXB),"Any event or condition that resulted in the nuclear power plant being in a condition that i

was outside the design basis of the plant." This report describes the identification of one location inside the Unit 2 containment structure where internal containment structural members could have damaged the containment liner during a safe shutdown earthquake (SSE), contrary to the plant design basis which requires containment integrity to be maintained during a SSE.

Please contact us if you require additional information.

Sincerely, Douglas F. Johnson Manager - Regulatory Services & Licensing

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NRC Resident Inspector NRC Regional Administrator 9702110460 970206 PDR ADOCK 05000301 S

PDR bhN A subsMhn af Hinwsh Ency Gepuativi

Licensee Event Report

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		Reporting criterion
05000266/LER-1997-001, :on 970108,safety Injection Delay Times Exceeded Design Basis Values.Caused by Degraded Voltage Conditions.Licensee Engineers Will Prepare FSAR Change Requests to Reflect LBLOCA Evaluation	on 970108,safety Injection Delay Times Exceeded Design Basis Values.Caused by Degraded Voltage Conditions.Licensee Engineers Will Prepare FSAR Change Requests to Reflect LBLOCA Evaluation	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1997-001, Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake	Forwards LER 97-001-00,re Containment Structure Where Internal Containment Structural Members Could Have Damaged Containment Liner During Safe Shutdown Earthquake
05000301/LER-1997-001-01, :on 970107,containment Liner Clearance Was Not IAW Plant Design Basis.Caused by Void Between Containment Liner & Concrete Containment Structure.Inspected Containment	on 970107,containment Liner Clearance Was Not IAW Plant Design Basis.Caused by Void Between Containment Liner & Concrete Containment Structure.Inspected Containment	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000266/LER-1997-002, :on 970109,potential to Overpressurize Piping Between Containment Isolation Valves Occurred.Caused by Original Design Not Providing Overpressure Protection for Piping.Review Completed	on 970109,potential to Overpressurize Piping Between Containment Isolation Valves Occurred.Caused by Original Design Not Providing Overpressure Protection for Piping.Review Completed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1997-002-01, :on 970415,potential Reactor Coolant Sys Branch Connection Stresses Beyond Design Basis,Indicated.Caused by Mod Initiated to Remove RTD Bypass Line Isolation Valves. Stress Analysis Conducted on RTD Bypass Piping	on 970415,potential Reactor Coolant Sys Branch Connection Stresses Beyond Design Basis,Indicated.Caused by Mod Initiated to Remove RTD Bypass Line Isolation Valves. Stress Analysis Conducted on RTD Bypass Piping	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-003, :on 970109,did Not Perform Leak Test on Spare Containment Penetrations Per Ts.Caused by Lack of Routine Testing.Tested Penetrations W/Satisfactory Results	on 970109,did Not Perform Leak Test on Spare Containment Penetrations Per Ts.Caused by Lack of Routine Testing.Tested Penetrations W/Satisfactory Results	10 CFR 50.73(a)(2)(1)
05000301/LER-1997-004-01, :on 970729,declared RHR Loop Inoperable Due to CCW Leak.Caused by Failure of RHR Heat Exchanger CCW Piping. Repaired Piping & Declared RHR Loop Operable	on 970729,declared RHR Loop Inoperable Due to CCW Leak.Caused by Failure of RHR Heat Exchanger CCW Piping. Repaired Piping & Declared RHR Loop Operable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-004, :on 970113,potential for Particular Common Mode Failure That Could Affect Opposite Trains of Unit 2 Safeguards Equipment Was Noted.Caused by Lack of Physical Separation.Replaced Subject Circuit Breakers	on 970113,potential for Particular Common Mode Failure That Could Affect Opposite Trains of Unit 2 Safeguards Equipment Was Noted.Caused by Lack of Physical Separation.Replaced Subject Circuit Breakers	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000301/LER-1997-005-01, :on 970806,RHR Pump Was Declared Inoperable Due to Abnormal Seal Leakage from Loop a RHR 2P-10A.Repaired RHR Pump	on 970806,RHR Pump Was Declared Inoperable Due to Abnormal Seal Leakage from Loop a RHR 2P-10A.Repaired RHR Pump	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-005, :on 970116,1SI-852A Was Not Tested IAW Inservice Test Program Required by Tss.Caused Because Condition Revealed That Valve 1SI-852A Had Not Been Completely Tested.Tests Will Be Reviewed	on 970116,1SI-852A Was Not Tested IAW Inservice Test Program Required by Tss.Caused Because Condition Revealed That Valve 1SI-852A Had Not Been Completely Tested.Tests Will Be Reviewed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000266/LER-1997-006, :on 970120,refueling Cavity Drain Failed During Loca.Caused by Inadequate Evaluation of Original Design.Design of Refueling Cavity Drains Was Revised with Respect Capability to Withstand an Earthquake	on 970120,refueling Cavity Drain Failed During Loca.Caused by Inadequate Evaluation of Original Design.Design of Refueling Cavity Drains Was Revised with Respect Capability to Withstand an Earthquake	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-007, :on 970124,determined That Potential Existed for EDG Overload Condition.Caused by Failure to Recognize This Condition When Plants Initially Licensed W/Two Edgs. Implemented Procedure Changes	on 970124,determined That Potential Existed for EDG Overload Condition.Caused by Failure to Recognize This Condition When Plants Initially Licensed W/Two Edgs. Implemented Procedure Changes	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-008, :on 970131,non-seismic Ductwork Located Above safety-related Equipment in Containment Occurred.Caused by Incomplete Seismic Evaluation.Mods Will Be Completed During Current Unit 2 Refueling Outage	on 970131,non-seismic Ductwork Located Above safety-related Equipment in Containment Occurred.Caused by Incomplete Seismic Evaluation.Mods Will Be Completed During Current Unit 2 Refueling Outage	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1997-009, :on 970214,potential for Safety Injection Failure During Filling of Safety Injection Accumulator Discovered.Caused by Situation Not Adequately Covered by Procedures.Procedure OI-100 Revised	on 970214,potential for Safety Injection Failure During Filling of Safety Injection Accumulator Discovered.Caused by Situation Not Adequately Covered by Procedures.Procedure OI-100 Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1997-010, :on 970219,svc Water & Component Cooling Water TS Action Requirements Were Not Met.Caused Because Licensee Did Not Comply W/Cold Shutdown Requirements of TS 15.3.3.C.2 & 15.3.3.D.2.Evaluations Were Performed	on 970219,svc Water & Component Cooling Water TS Action Requirements Were Not Met.Caused Because Licensee Did Not Comply W/Cold Shutdown Requirements of TS 15.3.3.C.2 & 15.3.3.D.2.Evaluations Were Performed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-011, :on 970305,containment Fan Cooler Accident Fans Were Not Tested in Accordance with Tss.Caused by non-conservative Interpretation of Literal Requirements of Tss.Unit 1 & 2 Accident Fans Were Tested	on 970305,containment Fan Cooler Accident Fans Were Not Tested in Accordance with Tss.Caused by non-conservative Interpretation of Literal Requirements of Tss.Unit 1 & 2 Accident Fans Were Tested	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000266/LER-1997-012, :on 970304,diesel-drive Fire Pump Day Tank Not Sampled IAW TSs.Non-conservative Interpretation of TS Led to Failure.Day Tank T-30 Sample Was Drawn & Analyzed W/Satisfactory Results	on 970304,diesel-drive Fire Pump Day Tank Not Sampled IAW TSs.Non-conservative Interpretation of TS Led to Failure.Day Tank T-30 Sample Was Drawn & Analyzed W/Satisfactory Results	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1)
05000266/LER-1997-013, :on 970304,CCWS Found Not in Accordance W/ Plant Design Basis.Caused by Inoperable Valve Due to Overtorquing in Closed position.Cross-tie Will Be Resolved	on 970304,CCWS Found Not in Accordance W/ Plant Design Basis.Caused by Inoperable Valve Due to Overtorquing in Closed position.Cross-tie Will Be Resolved	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-013-01, Forwards Suppl LER 97-013-01,re Component Cooling Water Sys Not IAW Plant Design Basis.Rept Replaces LER 97-013-00 in Its Entirety & Includes Addl Similar Occurrence Not Previously Reported to NRC	Forwards Suppl LER 97-013-01,re Component Cooling Water Sys Not IAW Plant Design Basis.Rept Replaces LER 97-013-00 in Its Entirety & Includes Addl Similar Occurrence Not Previously Reported to NRC	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-014, :on 970321,auxiliary Feedwater Sys Inoperability Due to Loss of Instrument Air.Design Mods Initiated,Providing Pneumatic Supply to Control Valves	on 970321,auxiliary Feedwater Sys Inoperability Due to Loss of Instrument Air.Design Mods Initiated,Providing Pneumatic Supply to Control Valves	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000266/LER-1997-015, :on 970324,control Room Ventilation Sys Declared Inoperable Due to Failures of Backdraft Damper & Vent Duct Access Door.Backdraft Damper,Replaced	on 970324,control Room Ventilation Sys Declared Inoperable Due to Failures of Backdraft Damper & Vent Duct Access Door.Backdraft Damper,Replaced	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1997-016, :on 970325,SG Level Logic Was Not Tested IAW Ts.Caused by Nonconservative Interpretation of Tss.Ts Amends Proposed to Provide Consistency Between Test Requirements & LCO Associated W/Sg Tests	on 970325,SG Level Logic Was Not Tested IAW Ts.Caused by Nonconservative Interpretation of Tss.Ts Amends Proposed to Provide Consistency Between Test Requirements & LCO Associated W/Sg Tests	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-017, :on 920508,containment Third Door Was Blocked Open During Refueling Operations.Caused by Interpretation That Movement of Core Components Per TS Definitions Rather than Literal Wording.Routine Maintenance Procedure Revised	on 920508,containment Third Door Was Blocked Open During Refueling Operations.Caused by Interpretation That Movement of Core Components Per TS Definitions Rather than Literal Wording.Routine Maintenance Procedure Revised	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1997-018, :on 970403,potential for RHR Overpressure During Accidents Was Discovered.Original Design Did Not Provide Overpressure Protection for Isolated Piping Section. Evaluation Was Performed to Determine Stress on Piping	on 970403,potential for RHR Overpressure During Accidents Was Discovered.Original Design Did Not Provide Overpressure Protection for Isolated Piping Section. Evaluation Was Performed to Determine Stress on Piping	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1997-019, :on 970404,RHR Not Aligned IAW TS Requirements. Caused by non-conservative Decision Making & Not Recognizing When TS Were Not Controlling Plant Operations.Pbnp Mgt Philosophy Re TS Interpretations Changed to Minimize Use	on 970404,RHR Not Aligned IAW TS Requirements. Caused by non-conservative Decision Making & Not Recognizing When TS Were Not Controlling Plant Operations.Pbnp Mgt Philosophy Re TS Interpretations Changed to Minimize Use	10 CFR 50.73(a)(2)(1)
05000266/LER-1997-020-01, Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected	Forwards LER 97-020-01,describing Plant Conditions in Which Ability to Achieve & Maintain Safe Shutdown in Event of Postulated Fire May Have Been Adversely Affected	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
05000266/LER-1997-021, :on 970430,determined That Spent Fuel Pool Cooling Sys Was Not in Accordance W/Plant Design Basis.Cause Indeterminate.Closed & re-tagged Valves SF-27 & SF-28 & Investigated Basis for Fsar,App a	on 970430,determined That Spent Fuel Pool Cooling Sys Was Not in Accordance W/Plant Design Basis.Cause Indeterminate.Closed & re-tagged Valves SF-27 & SF-28 & Investigated Basis for Fsar,App a	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-022, :on 970507,discovered That Postulated Control Room Fire May Cause Electrical Hot Short That Disables Limit or Torque Switches for Certain Movs.Mods Initiated to Remedy Condition	on 970507,discovered That Postulated Control Room Fire May Cause Electrical Hot Short That Disables Limit or Torque Switches for Certain Movs.Mods Initiated to Remedy Condition	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
05000266/LER-1997-023, :on 970508,discovered Noncompliant Emergency Lighting for Postulated App R Fires.Caused by Alternative Provisions Made in Original Safe Shutdown Analysis.Emergency Lights Will Be Installed	on 970508,discovered Noncompliant Emergency Lighting for Postulated App R Fires.Caused by Alternative Provisions Made in Original Safe Shutdown Analysis.Emergency Lights Will Be Installed	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000266/LER-1997-024, :on 970501,determined Post Accident Sampling Sys Degradation.Caused by Inadequate Design Review.Will Upgrade Containment Atmosphere Sample Sys & Will Perform Mod to Reduce Dose within GDC 19 Dose Limits	on 970501,determined Post Accident Sampling Sys Degradation.Caused by Inadequate Design Review.Will Upgrade Containment Atmosphere Sample Sys & Will Perform Mod to Reduce Dose within GDC 19 Dose Limits
05000266/LER-1997-025, :on 970520,pressurizer Level Was Controlled Higher than Assumed in Accident Analysis.Caused by Inappropriately Changing Procedures W/O Adequate Consideration.Listed Affected Procedures Will Be Revised	on 970520,pressurizer Level Was Controlled Higher than Assumed in Accident Analysis.Caused by Inappropriately Changing Procedures W/O Adequate Consideration.Listed Affected Procedures Will Be Revised	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1997-026, :on 970521,discovered TS Violation of Operability Requirement of MSL Isolation.Caused by Inadequate Consideration for Operability of All Required Functions.Verified Low RCS Sys Average Temp	on 970521,discovered TS Violation of Operability Requirement of MSL Isolation.Caused by Inadequate Consideration for Operability of All Required Functions.Verified Low RCS Sys Average Temp	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-027, :on 970521,non-environmentally Qualified Matl Existed in Containment Hatch Applications.Caused by Inadequate Design Review.Mods Will Be Performed to Remove Existing Teflon Material	on 970521,non-environmentally Qualified Matl Existed in Containment Hatch Applications.Caused by Inadequate Design Review.Mods Will Be Performed to Remove Existing Teflon Material
05000266/LER-1997-031, :on 970619,discovered That Auxiliary Feedwater (AFW) Pump Low Suction Pressure Trip Setpoints May Not Ensure Adequate Suction Pressure Protection for AFW Pumps Following Tornado Event.Caused by Inadequate Design	on 970619,discovered That Auxiliary Feedwater (AFW) Pump Low Suction Pressure Trip Setpoints May Not Ensure Adequate Suction Pressure Protection for AFW Pumps Following Tornado Event.Caused by Inadequate Design	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1997-032, :on 970630,discovered Inadequately Rated Electrical Buses Could Disable Switchgear & Cause Secondary Fires.Caused by Characteristic of Original Design. Established twice-per-shift Fire Watches	on 970630,discovered Inadequately Rated Electrical Buses Could Disable Switchgear & Cause Secondary Fires.Caused by Characteristic of Original Design. Established twice-per-shift Fire Watches	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000266/LER-1997-034, :on 970707,discovered Unplanned Loss of Voltage on Train B Safeguards Buses.Caused by Inadequate Design & Design Review for Installation of New Train B Edgs.Incorrect Wiring Reworked	on 970707,discovered Unplanned Loss of Voltage on Train B Safeguards Buses.Caused by Inadequate Design & Design Review for Installation of New Train B Edgs.Incorrect Wiring Reworked	10 CFR 50.73(a)(2)(iv), System Actuation
05000266/LER-1997-035, :on 970516,discovered Inadequate Seismic Support for Reactor Coolant Pump Rotor Stand.Caused by Rotor Stand Being Stored Since Initial Plant Construction.Moved Rotor Stand & Verified as Seismically Adequate	on 970516,discovered Inadequate Seismic Support for Reactor Coolant Pump Rotor Stand.Caused by Rotor Stand Being Stored Since Initial Plant Construction.Moved Rotor Stand & Verified as Seismically Adequate	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000266/LER-1997-036, :on 970826,potential Common Mode Failure in DC Power Supply Which Could Disable AFW Sys Was Noted.Caused by Inadequate Design & Design Review.Plant Mods Were Performed to Eliminate Potential Common Mode Failure	on 970826,potential Common Mode Failure in DC Power Supply Which Could Disable AFW Sys Was Noted.Caused by Inadequate Design & Design Review.Plant Mods Were Performed to Eliminate Potential Common Mode Failure
05000266/LER-1997-037, :on 970903,potential Failure of EDG Load Sequence Occurred.Caused by Inadequate Design of EDG Load Sequencing Logic.Mod Restored Operability of EDG During Load Sequencing	on 970903,potential Failure of EDG Load Sequence Occurred.Caused by Inadequate Design of EDG Load Sequencing Logic.Mod Restored Operability of EDG During Load Sequencing
05000266/LER-1997-038, :on 970926,determined That Inoperability of Standby Emergency Power Placed Unit 2 in 7-day Lco.Caused by Failure That Occurred When EDG G-03 Was Shutdown.Repaired Governor & Returned EDG G-03 to Service	on 970926,determined That Inoperability of Standby Emergency Power Placed Unit 2 in 7-day Lco.Caused by Failure That Occurred When EDG G-03 Was Shutdown.Repaired Governor & Returned EDG G-03 to Service	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-039-01, :on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored	on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-039, Forwards LER 97-039-00 Re RHR Loop Inoperable,Due to Inoperable CCW Pump.New Commitments within Rept Indicated in Italics	Forwards LER 97-039-00 Re RHR Loop Inoperable,Due to Inoperable CCW Pump.New Commitments within Rept Indicated in Italics	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000266/LER-1997-040-01, Forwards LER 97-040-01 Which Documents Event That Occurred at Point Beach Nuclear Plant,Unit 1.Commitments Made within Ltr,Encl	Forwards LER 97-040-01 Which Documents Event That Occurred at Point Beach Nuclear Plant,Unit 1.Commitments Made within Ltr,Encl	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000266/LER-1997-041, :on 971023,potential Common Mode Failure in Afws Control Circuits Was Noted.Caused by AFW Control Circuits Installed by Plant Mods.Temporary Mods Will Restore Physical Separation for Cables	on 971023,potential Common Mode Failure in Afws Control Circuits Was Noted.Caused by AFW Control Circuits Installed by Plant Mods.Temporary Mods Will Restore Physical Separation for Cables
05000266/LER-1997-042, :on 971030,discovered That Upper Containment Personnel Air Interlock Had Been Inoperable.Caused by Removal of Remote Operating Gear.Reinstalled Remote Operating Connector Gear	on 971030,discovered That Upper Containment Personnel Air Interlock Had Been Inoperable.Caused by Removal of Remote Operating Gear.Reinstalled Remote Operating Connector Gear	10 CFR 50.73(a)(2)(1)
05000266/LER-1997-043-01, Forwards LER 97-043-01,re Discovery That TS Surveillance of Reactor Trip Sys Interlocks Were Not Adequate. Supplemental Info Is Provided at End of Rept.Previous Commitments Made within Rept Also Encl	Forwards LER 97-043-01,re Discovery That TS Surveillance of Reactor Trip Sys Interlocks Were Not Adequate. Supplemental Info Is Provided at End of Rept.Previous Commitments Made within Rept Also Encl	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000266/LER-1997-044, :on 971216,use of Dedicated Operators During IST of Containment Spray Sys Constituted Operation Prohibited by Ts.Caused by Improper Consideration for Use of Dedicated Operators.Revised Procedures	on 971216,use of Dedicated Operators During IST of Containment Spray Sys Constituted Operation Prohibited by Ts.Caused by Improper Consideration for Use of Dedicated Operators.Revised Procedures

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